ML20149L774: Difference between revisions

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| document type = INTERNAL OR EXTERNAL MEMORANDUM, MEMORANDUMS-CORRESPONDENCE
| document type = INTERNAL OR EXTERNAL MEMORANDUM, MEMORANDUMS-CORRESPONDENCE
| page count = 1
| page count = 1
| project = TAC:M89353
| stage = Other
}}
}}


=Text=
=Text=
{{#Wiki_filter:-   .    . _
{{#Wiki_filter:-
pn ta4                                                                           UNITED STATES                               ~
pn ta4 UNITED STATES
y             *g                                                   NUCLEAR REGULATORY COMMISSION l!             $'                                                                      REclON IV 611 RYAN PLAZA DRIVE, SUITE 400 ARLINGTON, TEXAS 76011-8064 E 151996 MEMORANDUM T0:             Seymour H. Weiss, Director Non-Power Reactors and Decommissioning Project Directorate Division of Operating Reactor Support Office of Nuclear Reactor Regulati3 FROM:                     Thomas P. Gwynn, Director                                                       '
~
                                                                                                                      <  i Division of Reactor Safe Q
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*g NUCLEAR REGULATORY COMMISSION l!
REclON IV 611 RYAN PLAZA DRIVE, SUITE 400 ARLINGTON, TEXAS 76011-8064 E 151996 MEMORANDUM T0:
Seymour H. Weiss, Director Non-Power Reactors and Decommissioning Project Directorate Division of Operating Reactor Support Office of Nuclear Reactor Regulati3 FROM:
Thomas P. Gwynn, Director i
Division of Reactor Safe Q


==SUBJECT:==
==SUBJECT:==
FINAL SURVEY OF BRIGHAM YOUNG UNIVERSITY RESEARCH REACTOR (TAC NO. M89353), REFERENCE DOCKET NO. 50-262 This, refers to your May 9, 1994, memorandum which requested that Region IV:
FINAL SURVEY OF BRIGHAM YOUNG UNIVERSITY RESEARCH REACTOR (TAC NO. M89353), REFERENCE DOCKET NO. 50-262 This, refers to your May 9, 1994, memorandum which requested that Region IV:
(1) review the Final Decommission Survey for the Brigham Young University L-77 research reactor, (2) arrange for Oak Ridge Institute for Science and Education (0 RISE) to conduct a final confirmatory measurement survey of the facility, and (3) recommend whether Facility License R-109 can be terminated.
(1) review the Final Decommission Survey for the Brigham Young University L-77 research reactor, (2) arrange for Oak Ridge Institute for Science and Education (0 RISE) to conduct a final confirmatory measurement survey of the facility, and (3) recommend whether Facility License R-109 can be terminated.
We accompanied ORISE personnel to Brigham Young University on April 10-11, 1996, to observe them perform an independent survey of the L-77 reactor components and the reactor facility. Our review of the licensee and ORISE                                                             i survey results verified that:                                                 (1) residual surface contamination levels for reactor components and the facility were less than the values in NRC Regulatory Guide 1.86-Table 1, (2) gamma radiation levels were less than 5 micro-rem /hr above background at I meter from component and facility surfaces, and (3) all byproduct and special nuclear material on Facility License R-109 was transferred or properly disposed of to another license authorized to receive the material. A copy of ORISE's final survey report dated July 10, 1996, is' attached.
We accompanied ORISE personnel to Brigham Young University on April 10-11, 1996, to observe them perform an independent survey of the L-77 reactor components and the reactor facility. Our review of the licensee and ORISE i
survey results verified that:
(1) residual surface contamination levels for reactor components and the facility were less than the values in NRC Regulatory Guide 1.86-Table 1, (2) gamma radiation levels were less than 5 micro-rem /hr above background at I meter from component and facility surfaces, and (3) all byproduct and special nuclear material on Facility License R-109 was transferred or properly disposed of to another license authorized to receive the material. A copy of ORISE's final survey report dated July 10, 1996, is' attached.
Based on our review of the survey results, we recommend that the reactor components and the facility be released for unrestricted use and that Facility License R-109 be terminated.
Based on our review of the survey results, we recommend that the reactor components and the facility be released for unrestricted use and that Facility License R-109 be terminated.


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As stated cc w/ attachment:
As stated cc w/ attachment:
A. adams, NRR, 0-118-20 1
A. adams, NRR, 0-118-20 1
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i I)-[i' 9611180077 960715 P
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Latest revision as of 08:46, 11 December 2024

Forwards Final Survey of Brigham Young Univ L-77 Research Reactor
ML20149L774
Person / Time
Site: 05000262
Issue date: 07/15/1996
From: Gwynn T
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To: Weiss S
NRC (Affiliation Not Assigned)
Shared Package
ML20149L775 List:
References
TAC-M89353, NUDOCS 9611180077
Download: ML20149L774 (1)


Text

-

pn ta4 UNITED STATES

~

y

  • g NUCLEAR REGULATORY COMMISSION l!

REclON IV 611 RYAN PLAZA DRIVE, SUITE 400 ARLINGTON, TEXAS 76011-8064 E 151996 MEMORANDUM T0:

Seymour H. Weiss, Director Non-Power Reactors and Decommissioning Project Directorate Division of Operating Reactor Support Office of Nuclear Reactor Regulati3 FROM:

Thomas P. Gwynn, Director i

Division of Reactor Safe Q

SUBJECT:

FINAL SURVEY OF BRIGHAM YOUNG UNIVERSITY RESEARCH REACTOR (TAC NO. M89353), REFERENCE DOCKET NO. 50-262 This, refers to your May 9, 1994, memorandum which requested that Region IV:

(1) review the Final Decommission Survey for the Brigham Young University L-77 research reactor, (2) arrange for Oak Ridge Institute for Science and Education (0 RISE) to conduct a final confirmatory measurement survey of the facility, and (3) recommend whether Facility License R-109 can be terminated.

We accompanied ORISE personnel to Brigham Young University on April 10-11, 1996, to observe them perform an independent survey of the L-77 reactor components and the reactor facility. Our review of the licensee and ORISE i

survey results verified that:

(1) residual surface contamination levels for reactor components and the facility were less than the values in NRC Regulatory Guide 1.86-Table 1, (2) gamma radiation levels were less than 5 micro-rem /hr above background at I meter from component and facility surfaces, and (3) all byproduct and special nuclear material on Facility License R-109 was transferred or properly disposed of to another license authorized to receive the material. A copy of ORISE's final survey report dated July 10, 1996, is' attached.

Based on our review of the survey results, we recommend that the reactor components and the facility be released for unrestricted use and that Facility License R-109 be terminated.

Attachment:

As stated cc w/ attachment:

A. adams, NRR, 0-118-20 1

i I)-[i' 9611180077 960715 P

PDR ADOCK 05000262

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V P

PDR o